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Category:MONTHLY OPERATING ANALYSIS REPORT
MONTHYEARML20217G3541999-09-30030 September 1999 Monthly Operating Repts for Sept 1999 for Pbaps,Units 2 & 3. with ML20212A5871999-08-31031 August 1999 Monthly Operating Repts for Aug 1999 for Peach Bottom,Units 2 & 3.With ML20210N7641999-07-31031 July 1999 Monthly Operating Repts for Jul 1999 for PBAPS Units 2 & 3. with ML20209H1121999-06-30030 June 1999 Monthly Operating Repts for June 1999 for Pbaps,Units 2 & 3. with ML20195H8841999-05-31031 May 1999 Monthly Operating Repts for May 1999 for Pbaps,Units 2 & 3. with ML20206N1661999-04-30030 April 1999 Monthly Operating Repts for Apr 1999 for Pbaps,Units 2 & 3. with ML20205P5851999-03-31031 March 1999 Monthly Operating Repts for Mar 1999 for Peach Bottom Units 2 & 3.With ML20207G9971999-02-28028 February 1999 Monthly Operating Repts for Feb 1999 for Peach Bottom Units 2 & 3.With ML20199E3471998-12-31031 December 1998 Monthly Operating Repts for Dec 1998 for Peach Bottom,Units 1 & 2.With ML20198B8591998-11-30030 November 1998 Monthly Operating Repts for Nov 1998 for Pbaps,Units 2 & 3. with ML20195E5341998-10-31031 October 1998 Monthly Operating Repts for Oct 1998 for Pbaps,Units 2 & 3. with ML20154H5541998-09-30030 September 1998 Monthly Operating Repts for Sept 1998 for Pbaps,Units 2 & 3. with ML20151Y2901998-08-31031 August 1998 Monthly Operating Repts for Aug 1998 for Pbaps,Units 2 & 3. with ML20237A5351998-07-31031 July 1998 Monthly Operating Repts for July 1998 for Pbaps,Units 2 & 3 ML20236M3471998-06-30030 June 1998 Monthly Operating Repts for June 1998 for Pbaps,Units 2 & 3 ML20248M3001998-05-31031 May 1998 Monthly Operating Repts for May 1998 for Pbaps,Units 2 & 3 ML20247G0721998-04-30030 April 1998 Monthly Operating Repts for Apr 1998 for Pbaps,Units 2 & 3 ML20216F3831998-03-31031 March 1998 Monthly Operating Repts for Mar 1998 for Peach Bottom,Units 2 & 3 ML20216G1991998-02-28028 February 1998 Monthly Operating Repts for Feb 1998 for Peach Bottom Atomic Power Station,Units 1 & 2 ML20202F7341998-01-31031 January 1998 Monthly Operating Repts for Jan 1998 for Pbaps,Units 2 & 3 ML20198N8851997-12-31031 December 1997 Monthly Operating Repts for Dec 1997 for Peach Bottom,Units 2 & 3 ML20203J7311997-11-30030 November 1997 Monthly Operating Repts for Nov 1997 for Pbaps,Units 2 & 3 ML20199D1241997-10-31031 October 1997 Monthly Operating Repts for Oct 1997 for Peach Bottom,Units 2 & 3 ML20198J8871997-09-30030 September 1997 Monthly Operating Repts for Sept 1997 for Pbaps,Units 2 & 3 ML20217A8061997-08-31031 August 1997 Monthly Operating Repts for Aug 1997 for Peach Bottom Units 2 & 3 ML20210J7111997-07-31031 July 1997 Monthly Operating Repts for Jul 1997 for Pbaps,Units 1 & 2 ML20141H2071997-06-30030 June 1997 Monthly Operating Repts for June 1997 for PBAPS ML20148K6251997-05-31031 May 1997 Monthly Operating Repts for May 1997 for Peach Bottom Atomic Power Station Units 2 & 3 ML20141D3691997-04-30030 April 1997 Monthly Operating Rept for Apr 1997 for Peach Bottom Units 2 & 3 ML20137V9731997-03-31031 March 1997 Monthly Operating Repts for Mar 1997 for Peach Bottom Atomic Power Station Units 2 & 3 ML20136G3671997-02-28028 February 1997 Monthly Operating Repts for Feb 1997 for PBAPS ML20138K5551997-01-31031 January 1997 Monthly Operating Repts for Jan 1997 for Peach Bottom Units 2 & 3 ML20133H6121996-12-31031 December 1996 Monthly Operating Repts for Dec 1996 for Peach Bottom 2 & 3 ML20132B9481996-11-30030 November 1996 Monthly Operating Repts for Nov 1996 for Peach Bottom Units 1 & 2 ML20134M0501996-10-31031 October 1996 Monthly Operating Repts for Oct 1996 for Peach Bottom Unit 2 & 3 ML20129A9871996-09-30030 September 1996 Monthly Operating Repts for Sept 1996 for Peach Bottom Unit 2 & 3 ML20117N1601996-08-31031 August 1996 Monthly Operating Repts for Aug 1996 for Peach Bottom Atomic Power Station Units 1 & 2 ML20116M1641996-07-31031 July 1996 Monthly Operating Repts for Jul 1996 for Peach Bottom Units 2 & 3 ML20115F8541996-06-30030 June 1996 Monthly Operating Repts for June 1996 for Peach Bottom Units 1 & 2 ML20116M1701996-06-30030 June 1996 Revised MOR for June 1996 for Peach Bottom Unit 3 ML20117M6781996-05-31031 May 1996 Monthly Operating Repts for May 1996 for Peach Bottom Atomic Power Station ML20117F8161996-04-30030 April 1996 Monthly Operating Repts for April 1996 for PBAPS ML20107D9381996-03-31031 March 1996 Monthly Operating Repts for March 1996 for PBAPS ML20106G8101996-02-29029 February 1996 Monthly Operating Repts for Feb 1996 for Peach Bottom Atomic Power Station Units 1 & 2 ML20149K9331996-01-31031 January 1996 Monthly Operating Repts for Jan 1996 for PBAPS Units 2 & 3 ML20096F4151995-12-31031 December 1995 Monthly Operating Repts for Dec 1995 for Pbaps,Units 2 & 3 ML20095G9381995-11-30030 November 1995 Monthly Operating Repts for Nov 1995 for PBAPS Units 2 & 3 ML20094L6301995-10-31031 October 1995 Monthly Operating Repts for Oct 1995 for Peach Bottom Units 2 & 3 ML20093G3571995-09-30030 September 1995 Monthly Operating Repts for Sept 1995 for PBAPS Units 1 & 2 ML20092G3231995-08-31031 August 1995 Monthly Operating Repts for Aug 1995 for Peach Bottom Units 2 & 3 1999-09-30
[Table view] Category:TEXT-SAFETY REPORT
MONTHYEAR05000278/LER-1999-005-03, :on 990920,uplanned Esfas During Planned Mod Activitives in Main CR Were Noted.Caused by Inattention to Detail by Individuals Performing Work.All CR Mods Were Ceased to Allow Review of Mod Work Packages.With1999-10-20020 October 1999
- on 990920,uplanned Esfas During Planned Mod Activitives in Main CR Were Noted.Caused by Inattention to Detail by Individuals Performing Work.All CR Mods Were Ceased to Allow Review of Mod Work Packages.With
ML20217K9931999-10-14014 October 1999 Safety Evaluation Supporting Amend 234 to License DPR-56 ML20217B4331999-10-0505 October 1999 Safety Evaluation Supporting Amend 233 to License DPR-56 05000278/LER-1999-004-03, :on 990901,3A RPS Bus Was Inadvertently Deenergized,During Planned Mod Activities on Main CR Panel. Caused by Electrician Failing to Self Check Work.All CR Work Was Ceased Immediately & Shutdown Meeting Held1999-10-0101 October 1999
- on 990901,3A RPS Bus Was Inadvertently Deenergized,During Planned Mod Activities on Main CR Panel. Caused by Electrician Failing to Self Check Work.All CR Work Was Ceased Immediately & Shutdown Meeting Held
ML20217G3541999-09-30030 September 1999 Monthly Operating Repts for Sept 1999 for Pbaps,Units 2 & 3. with ML20216H7091999-09-24024 September 1999 Safety Evaluation Supporting Amends 229 & 232 to Licenses DPR-44 & DPR-56,respectively ML15112A7681999-09-20020 September 1999 SER Accepting Revision 25 of Pump & Valve Inservice Testing Program,Third 10-year Interval for Plant,Units 1,2 & 3 ML20212D1281999-09-17017 September 1999 Safety Evaluation Supporting Proposed Alternatives CRR-03, 05,08,09,10 & 11 05000278/LER-1999-003-03, :on 990814,HPCIS Was Declared Inoperable Due to Erratic Behavior Resulting in Loss of Single High Train Safety Sys.Caused by Weakness in Procedural Guidance. Readjusted Hydraulic Governor Needle Valve.With1999-09-13013 September 1999
- on 990814,HPCIS Was Declared Inoperable Due to Erratic Behavior Resulting in Loss of Single High Train Safety Sys.Caused by Weakness in Procedural Guidance. Readjusted Hydraulic Governor Needle Valve.With
ML20212A5871999-08-31031 August 1999 Monthly Operating Repts for Aug 1999 for Peach Bottom,Units 2 & 3.With ML20211D5501999-08-23023 August 1999 Safety Evaluation Supporting Amends 228 & 231 to Licenses DPR-44 & DPR-56,respectively ML20212H6311999-08-19019 August 1999 Rev 2 to PECO-COLR-P2C13, COLR for Pbaps,Unit 2,Reload 12 Cycle 13 ML20210N7641999-07-31031 July 1999 Monthly Operating Repts for Jul 1999 for PBAPS Units 2 & 3. with 05000277/LER-1999-005-01, :on 990616,failure to Maintain Provisions of FP Program Occurred.Caused by Less than Adequate Engineering Rigor in Both Development & Review Analysis.Fire Watch Immediately Established.With1999-07-16016 July 1999
- on 990616,failure to Maintain Provisions of FP Program Occurred.Caused by Less than Adequate Engineering Rigor in Both Development & Review Analysis.Fire Watch Immediately Established.With
ML20209H1121999-06-30030 June 1999 Monthly Operating Repts for June 1999 for Pbaps,Units 2 & 3. with ML20195H8841999-05-31031 May 1999 Monthly Operating Repts for May 1999 for Pbaps,Units 2 & 3. with 05000278/LER-1999-002-02, :on 990406,safeguard Sys to Unrelated Door Was Inadvertently Disabled by Security Alarm Station Operator. Caused by Noncompliance with Procedures & Less than Adequate Shift Turnover.Briefed Personnel on Event.With1999-05-0606 May 1999
- on 990406,safeguard Sys to Unrelated Door Was Inadvertently Disabled by Security Alarm Station Operator. Caused by Noncompliance with Procedures & Less than Adequate Shift Turnover.Briefed Personnel on Event.With
ML20206N1661999-04-30030 April 1999 Monthly Operating Repts for Apr 1999 for Pbaps,Units 2 & 3. with ML20206A2921999-04-20020 April 1999 Safety Evaluation Concluding That Proposed Changes to EALs for PBAPS Are Consistent with Guidance in NUMARC/NESP-007 & Identified Deviations Meet Requirements of 10CFR50.47(b)(4) & App E to 10CFR50 05000278/LER-1999-001-03, :on 990312,ESF Actuation of Rcics Occurred Due to High Steam Flow Signal During Sys Restoration.Temporary Change to Restoration Procedure Was Initiated to Open RCIC Outboard Steam Isolation Valve in Smaller Increments1999-04-0808 April 1999
- on 990312,ESF Actuation of Rcics Occurred Due to High Steam Flow Signal During Sys Restoration.Temporary Change to Restoration Procedure Was Initiated to Open RCIC Outboard Steam Isolation Valve in Smaller Increments
ML20205K7411999-04-0707 April 1999 Safety Evaluation Supporting Amends 227 & 230 to Licenses DPR-44 & DPR-56,respectively ML20205P5851999-03-31031 March 1999 Monthly Operating Repts for Mar 1999 for Peach Bottom Units 2 & 3.With ML20207G9971999-02-28028 February 1999 Monthly Operating Repts for Feb 1999 for Peach Bottom Units 2 & 3.With 05000278/LER-1998-009-01, :on 981227,unplanned Esfa Were Noted.Caused by Transformer Insulator Failure.Replaced Failed Insulator. with1999-01-20020 January 1999
- on 981227,unplanned Esfa Were Noted.Caused by Transformer Insulator Failure.Replaced Failed Insulator. with
ML20206P1651998-12-31031 December 1998 Fire Protection for Operating Nuclear Power Plants, Section Iii.F, Automatic Fire Detection ML20199E3471998-12-31031 December 1998 Monthly Operating Repts for Dec 1998 for Peach Bottom,Units 1 & 2.With ML20206D3651998-12-31031 December 1998 1998 PBAPS Annual 10CFR50.59 & Commitment Rev Rept. with ML20205K0381998-12-31031 December 1998 PECO Energy 1998 Annual Rept. with ML20206D3591998-12-31031 December 1998 1998 PBAPS Annual 10CFR72.48 Rept. with 05000277/LER-1998-008-01, :on 981130,circuit Breaker SU-25 Tripped.Caused by Less than Adequate Procedural Guidance.Operators Verified Sys Integrity & Successfully Returned Sys to Svc.With1998-12-30030 December 1998
- on 981130,circuit Breaker SU-25 Tripped.Caused by Less than Adequate Procedural Guidance.Operators Verified Sys Integrity & Successfully Returned Sys to Svc.With
05000277/LER-1998-007-02, :on 981107,failure to Meet TS & Associated LCO Requirments of Absolute Difference in APRM & Calculated Power of Less than 2% Was Noted.Caused by Substitute Valves Being Used.Removed Substitute Valves.With1998-12-0404 December 1998
- on 981107,failure to Meet TS & Associated LCO Requirments of Absolute Difference in APRM & Calculated Power of Less than 2% Was Noted.Caused by Substitute Valves Being Used.Removed Substitute Valves.With
ML20196G7021998-12-0202 December 1998 SER Authorizing Proposed Alternative to Delay Exam of Reactor Pressure Vessel Shell Circumferential Welds by Two Operating Cycles ML20198B8591998-11-30030 November 1998 Monthly Operating Repts for Nov 1998 for Pbaps,Units 2 & 3. with ML20196E8261998-11-30030 November 1998 Response to NRC RAI Re Reactor Pressure Vessel Structural Integrity at Peach Bottom Units 2 & 3 05000278/LER-1998-005-03, :on 981025,inadvertent Unit 3 Electrical Bus E33 Trip (Esfa) During Performance of Unit 2 Electrical Bus E32 Surveillance Test Was Noted.Caused by Personnel Error. Sp S12M-54-E32-XXF4 Was Completed.With1998-11-20020 November 1998
- on 981025,inadvertent Unit 3 Electrical Bus E33 Trip (Esfa) During Performance of Unit 2 Electrical Bus E32 Surveillance Test Was Noted.Caused by Personnel Error. Sp S12M-54-E32-XXF4 Was Completed.With
ML20206R2571998-11-17017 November 1998 PBAPS Graded Exercise Scenario Manual (Sections 1.0 - 5.0) Emergency Preparedness 981117 Scenario P84 ML20198C6751998-11-0505 November 1998 Rev 3 to COLR for PBAPS Unit 3,Reload 11,Cycle 12 ML20195E5341998-10-31031 October 1998 Monthly Operating Repts for Oct 1998 for Pbaps,Units 2 & 3. with ML20155C6071998-10-26026 October 1998 Safety Evaluation Supporting Amend 226 to License DPR-44 ML20155C1681998-10-22022 October 1998 Safety Evaluation Accepting Proposed Alternative Plan for Exam of Reactor Pressure Vessel Shell Longitudinal Welds ML20155H7721998-10-12012 October 1998 Rev 1 to COLR for Peach Bottom Atomic Power Station Unit 2, Reload 12,Cycle 13 05000277/LER-1998-006-02, :on 980915,automatic RWCU Isolation Occurred While Placing RWCU Sys in Svc.Caused by Unexpected Surge of Water.Procedure Change Was Initiated to Open MO-2-12-74 & RWCU Sys Was Successfully Returned to Svc.With1998-10-0909 October 1998
- on 980915,automatic RWCU Isolation Occurred While Placing RWCU Sys in Svc.Caused by Unexpected Surge of Water.Procedure Change Was Initiated to Open MO-2-12-74 & RWCU Sys Was Successfully Returned to Svc.With
ML20154J2401998-10-0505 October 1998 Safety Evaluation Supporting Amends 224 & 228 to Licenses DPR-44 & DPR-56,respectively ML20154H4771998-10-0505 October 1998 Safety Evaluation Supporting Amends 225 & 229 to Licenses DPR-44 & DPR-56,respectively ML20154G6631998-10-0101 October 1998 Safety Evaluation Supporting Amends 223 & 227 to Licenses DPR-44 & DPR-56,respectively ML20154G6821998-10-0101 October 1998 SER Related to Request for Relief 01A-VRR-1 Re Inservice Testing of Automatic Depressurization Sys Safety Relief Valves at Peach Bottom Atomic Power Station,Units 2 & 3 ML20154H5541998-09-30030 September 1998 Monthly Operating Repts for Sept 1998 for Pbaps,Units 2 & 3. with 05000277/LER-1998-005-02, :on 980824,noted Failure to Meet TS Actions for Suppression chamber-to-drywell Vacuum Breaker Not Being Fully Seated.Caused by Personnel Failing to Take All TS Required Actions.Temporary Procedure Changes Were Made1998-09-18018 September 1998
- on 980824,noted Failure to Meet TS Actions for Suppression chamber-to-drywell Vacuum Breaker Not Being Fully Seated.Caused by Personnel Failing to Take All TS Required Actions.Temporary Procedure Changes Were Made
05000278/LER-1998-004-03, :on 980820,automatic RWCU Isolation Occurred While Placing B RWCU Sys Demineralizer in Svc.Caused by less-than-adequate Control of Equipment.Isolated B Demineralizer & Returned RWCU Sys to Svc1998-09-18018 September 1998
- on 980820,automatic RWCU Isolation Occurred While Placing B RWCU Sys Demineralizer in Svc.Caused by less-than-adequate Control of Equipment.Isolated B Demineralizer & Returned RWCU Sys to Svc
ML20153B9651998-09-14014 September 1998 Safety Evaluation Supporting Amend 9 to License DPR-12 1999-09-30
[Table view] |
Text
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Perch Bottom Atomic Power station A
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PECO NUCLEAR rem % vc- -
1848 Lay Road A Unit or PECO Entucy Detta. PA 17314-9032 717 456 7014 l
July 3,1996 U.S. Nuclear Regulatory Commission Document Control Desk t
Washington, D.C. 20555 Docket Nos. 50-277 and 50 278 Gentlemen:
i l
Enclosed is the monthly operating report for Peach Bottom Units 2 and 3 for the month of June 1996 forwarded pursuani to Technical Specification 5.6.4 under the guidance of Regulatory Guide 10.1, Revision 4.
Sincerely, M
Mark E. Wamer Director, Site Engineering i
Peach om Atomic Power Station MEW /JGH:Iph l
l Enclosures cc:
B.W. Gorman, Public Service Electric & Gas W.P. Domsife, Commonwealth of Pennsylvania R.I. McLean, State of Maryland T.T. Martin, Administrator, Region I, USNRC l
W.L. Schmidt, USNRC, Senior Resident inspector l
H.C. Schwemm, Atlantic Electric A.F. Kirby, Ill, Delmarva Power & Light i
INPO Records Center T. N. Mitchell i
1OO hk <
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ccn 96-14061 1
9607100126 960630 PDR ADOCK 05000277 i
R PDR
PEACH COTTOM ATOMIC POWER STATION NRC MONTHLY OPERATIONS
SUMMARY
June 1996 UNIT 2 During June the unit was at a lower power and lower efficiency due to coastdown. Unit 2 began the month at 83% power, on 6/9/96 RFP was removed from service. Also, the unit experienced unplanned losses due to BOP inefficiencies.
Unit 2 net generation for May was 582,556 MW.
UNIT 3 Unit 3 began the month of June at 62% power. Unit 3 losses were significant during the month.
The losses included a planned load drop on 5/31/96. The load drop allowed the following work to i
be performed: cleaning the MG set lube oil cooler and replacing the brushes, waterbox cleaning, 3B Reactor Feed Pump work, rod pattem adjustments, and MSIV testing. The load drop terminated on 6/3/96. The Unit remained at 100% power for the rest of the month until a planned load drop on 6/22/96. This load drop commenced in order to repair #4 CV EHC leak and MSV leak. During the load drop, testing revested a mechanical failure of the #2 Turbine Control Valve J
resulting in an unplanned unit outage which started on 6/23/96. The unit was retumed to power on 6/28/96.
Unit 3 net generation for June was 591,486 MW.
1 l
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Attachm:nt to Monthly Operating Report for June 1996 UNIT 2 REFUELING INFORMATION 1.
Name of facility:
Peach Bottom Unit 2 2.
Scheduled date for next refueling shutdown:
Reload 11 scheduled for September 13,1996.
3.
Scheduled date for restart following refueling:
Restart following refueling forecast for October 12,1996.
4.
Will refueling or resumption of operation therefore require a technical specification change or other license amendment?
Yes.
If answer is yes, what, in general, will these be?
1.10CFR50 Appendix J, Option B
- 2. Increase MCPR Value 5.
Scheduled date(s) for submitting proposed licensing action and supporting information:
Items 1 and 2 have been submitted for review and approval. NRC approval has been received for item 1.
6.
Important licensing considerations associated with refueling, e.g., new or different fuel design or l
supplier, unreviewed design or performance analysis methods, significant changes in fuel design, P
new operating procedures:
)
GE-13 Fuel Product Line will be utilized requiring a Tech Spec amendment.
a 7.
The number of fuel assemblies (a) in the core and (b) in the spent fuel storage pool:
(a) Core - 764 Fuel Assemblies (b) Fuel Pool-2436 Fuel Assemblies,52 Fuel Rods
Docket Ns. 50-277 t
l Attachm nt13 l
Monthly Operating l
Report for June 1996 l
Page 2 l
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UNIT 2 REFUELING INFORMATION (Continued) l l
8.
The present licensed spent fuel pool storage capacity and the size of any increase in licensed l
storage capacity that has been requested or is planned, in number of fuel assemblies:
l l
The spent fuel pool storage capacity has been relicensed for 3819 fuel assemblies.
1 9.
The projected date of the last refueling that can be discharged to the spent fuel pool assuming l
the present capacity:
September 2002 without %fi core offload capability.
September 1998 with full core offload capability.
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Docket N:. 50-278
l Monthly Operating l
Report for June 1996 j
1 l
UNIT 3 REFUELING INFORMATION 1.
Name of facility:
Peach Bottom Unit 3 l
2.
Scheduled date for next refueling shutdown:
Reload 11 scheduled for September 12,1997 3.
Scheduled date for restart following refueling Restart following refueling scheduled for October 11,1997 4.
Will refueling or resumption of operation thereafter require a technical specification change or other license amendment?
i l
N/A If answer is yes, what, in general, will these be?
1 l
5.
Scheduled date(s) for submitting proposed licensing action and supporting information:
6.
Important licensing considerations associated with refueling, e.g., new or different fuel design or l
supplier, unreviewed design or performance analysis methods, significant changes in fuel design, l
new operating procedures:
l l
N/A l
7.
The number of fuel assemblies (a) in the core and (b) in the spent fuel storage pool:
i (a) Core - 764 Fuel Assemblies (b) Fuel Pool-2485 Fuel Assemblies,16 Fuel Rods i
8.
The present licensed spent fuel pool storage capacity and the size of any increase in licensed storage capacity that has been requested or is planned, in number of fuel assemblies:
The spent fuel pool storage capacity has been relicensed for 3819 fuel assemblies.
~
Dock".t No. 50-278 Attachment to Monthly Operating Report for June 1996 3
Page 2 UNIT 3 REFUELING INFORMATION (Continued) 9.
The projected date of the last refueling that can be discharged to the spent fuel pool assuming the present capacity:
September 2003 without full core offload cap &bility.
September 1999 with full core offload capability.
4
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_.._.m..._..
_. _ _ _ _.... _. - ~ _ - - _ -
AVERAGE DAILY POWER LEVEL DOCKET NO. 50-277 UNIT PEACH BOTTOM UNIT 2 DATE JULY 11,1996 COMPANY PECOENERGYCOMPANY L P.HYDRICK e-BUSINESS SERVICES SITE SUPPORT DMSION PEACH BOTTOM ATOMIC POWER STATION f
TELEPHONE (717)4564383 I
MONTH JUNE,1996 DAY AVERAGE DAILY POWER LEVEL DAY AVERAGE DAILY POWER LEVEL (MWE-NET)
(MWEWET)
[
i 1
879 17 801 2
892 18 797 i
3 863 19 797 4
864 20 789 f
5 866 21 784 i
6 854 22 789 i
t 7
849 23 777 i
8 845 24 789 9
833 25 764 to 845 26 750 11 821 27 789 l
12 820 28 736 s
13 804 29 753 14 805 30 749 15 804 16 797 4
k
AVERAGE DAILY POWER LEVEL DOCKET NO. 50-278 UNIT PEACH BOTTOM UNIT 3 DATE JULY 11,1996 COMPANY PECO ENERGY COMPANY L P.HYDRICK BUSINESS SERVICES SITE SUPPORT DMSION PEACH BOTTOM ATOMIC POWER STATION TELEPHONE (717)4564383 MONTH JUNE,1996 DAY AVERAGE DAtLY POWER LEVEL DAY AVERAGE DAILY POWER LEVEL (MWE-NET)
(MWE-NET) 1 352 17 1106 2
845 18 1097 3
1098 19 1106 4
1114 20 1101 5
1112 21 1106 6
1109 22 295 7
1107 23 115 8
1108 24 0
9 1104 25 0
10 1120 26 0
11 1096 27 0
12 1100 28 326 13 1100 29 707 14 1103 30 1045 15 1106 16 1106
OPERATING DATA REPORT DOCKET NO. 50 -277 DATE JULY 11,1996 COMPLETED BY PECO ENERGY COMPANY L P. HYDRICK BUSINESS SERVICES SITE SUPPORT DMSION PEACH BOTTOM ATOMIC POWER STATION TELEPHONE (717)456 4383 OPERATING STATUS
- 1. UNIT NAME:
PEAC_H BOTTOM UNIT 2 NOTES:
- 2. REPORTING PERIOD:
JU_N_EJ996
- 3. LICENSED THERMAL POWER (MWT) 3458
- 4. NAMEPLATE RATING (GROSS MWE):
1221
- 5. DESIGN ELECTRICAL RATING (NET MWE):
1119
- 6. MAXIMUM DEPENDABLE CAPACITY (GROSS MWE):
115_0
- 7. MAXIMUM DEPENDABLE CAPACITY (NET MWE):
1093
- 8. IF CHANGES OCCUR IN CAPACITY RATINGS (ITEMS 3 THROUGH 7 ) SINCE LAST REPORT, GIVE REASONS:
- 9. POWER LEVEL TO WHICH RESTRICTED, IF ANY (NET MWE):
- 10. REASONS FOR RESTRICTIONS,IF ANY:
THIS MONTH YR-TO-DATE CUMULATIVE
- 11. HOURS IN REPORTING PERIOD 720 4,367 192,767 I
- 12. NUMBER OF HOURS REACTOR WAS CRITICAL 720.0 4,367.0 126,962.5
- 13. REACTOR RESERVE SHUTDOWN HOURS 0.0 0.0 0.0
- 14. HOURS GENERATOR ON-LINE 720.0 4,367.0 122,968.2 t
- 15. UNIT RESERVE SHUTDOWN HOURS 0.0 0.0
~
0.0
- 16. GROSS THERMAL ENERGY GENERATED (MWH) 1,923.110 13,998,168 371,574,211 17 GROSS ELECTRICAL ENERGY GENERATED (MWH) 808,000 4,503,500 122,133,290
- 18. NET ELECTRICAL ENERGY GENERATED (MWH) 582,556 4,448,127 117,254,022 PAGE 1 OF 2
. ~ ~. - ~. _.. ~ -, _
i t
OPERATING DATA REPORT (CONTINUED)
DOCKET NO.
50 -277 DATE JULY 11,1996
{
(
THIS MONTH YR-TO-DATE CUMULATIVE
- 19. UNIT SERVICE FACTOR 100.0 %
100.0 %
63.8 %
j
- 20. UNIT AVAILABILITY FACTOR 100.0 %
100.0 %
63.8 %
- 21. UNIT CAPACITY FACTOR (USING MDC NET) 74.0 %
93.2 %
57.6 %
- 22. UNIT CAPACITY FACTOR (USING DER NET) 72.3 %
91.0 %
56.8 %
- 23. UNIT FORCED OUTAGE RATE
.0 %
.0 %
11.9 %
?
- 24. SHUTDOWNS SCHEDULED OVER THE NEXT 6 MONTHS (TYPE, DATE AND DURATION OF EACH):
j Refueling culage seedule to begin 9/13196, Durabon 29 days i
- 25. IF SHUTDOWN AT THE ENO OF REPORT PERIOD, ESTIMATED DATE OF STARTUP:
E
- 26. UNITS IN TEST STATUS (PRIOR TO COMMERCIAL OPERATIONS):
FORECAST ACHIEVED INITIAL CRITICAU1Y 09/16/73
[
t INITIAL ELECTRICITY 92/18/74 t
COMMERCIAL OPERATION 07A15/74 I
f e
9 h
t PAGE 2 OF 2 L
OPERATING DATA REPORT DOCKET NO. 50- 278 DATE JULY 11,1998 i
COMPLETED BY PECO ENERGY COMPANY L P.HYDRICK BUSINESS SERVICES
[
SITE SUPPORT DIVISION t
PEACH BOTTOM ATOMIC POWER STATION TELEPHONE (717) 456-4383 OPERATING STATUS
- 1. UNIT NAME.
PEACH BOTTOM UNIT 3 NOTES:
- 2. REPORTING PERIOD:
JUNE,1998
- 3. LICENSED THERMAL POWER (MWT) 3458
- 4. NAMEPLATE RATING (GROSS MWE):
1221
- 5. DESIGN ELECTRICAL RATING (NET MWE):
1119 1
- 6. MAXIMUM DEPENDABLE CAPACITY (GROSS MWE):
1159 7, MAXIMUM DEPENDABLE CAPACITY (NET MWE):
1093
- 8. IF CHANGES OCCUR IN CAPACITY RATINGS (ITEMS 3 THROUGH 7 ) SINCE LAST REPORT, GIVE REASONS:
- 9. POWER LEVEL TO WHICH RESlillCTED,IF ANY(NET MWE):
- 10. REASONS FOR RESTRICTIONS,IF ANY:
THIS MONTH YR-TO-DATE CUMULATNE
{
- 11. HOURS IN REPORTING PERIOD 720 4,387 188,683
- 12. NUMBER OF HOURS REACTOR WAS CRITICAL 631.1 4,278.1 125,565.3 2
- 13. REACTOR RESERVE SHUTDOWN HOURS 0.0 0.0 0.0
- 14. HOURS GENERATOR ON-LINE 613.0 4,210.0 122,0182
- 15. UNIT RESERVE SHUTDOWN HOURS 0.0 0.0 0.0
- 16. GROSS THERMAL ENERGY GENERATED (MWH) 1,715,129 13,998,834 383,685,292 7
- 17. GROSS ELECTRICAL ENERGY GENERATED (MWH) 612,000 4,678,800 119,298,032
- 18. NET ELECTRICAL ENERGY GENERATED (MWH) 501,408 4,547,373 114,561,225 PAGE 1 OF 2
OPERATING DATA REPORT (CONTINUED)
DOCKET NO.
50.V8 i
DATE JULY ti.1996 THIS MONTH YR-TO-DATE CicMULATIVE
- 19. UNIT SERVICE FACTOR 85.1 %
96.4 %
64.7 %
- 20. UNIT AVAILABILITY FACTOR 85.1 %
98.4 %
64.7 %
- 21. UNIT CAPACITY FACTOR (USING MDC NET) 752 %
95.3 %
58.5 %
- 22. UNIT CAPACITY FACTOR (USING DER NET) 73.4 %
93.1 %
56.9 %
- 23. UNIT FORCED OUTAGE RATE 14.9 %
3.6 %
10.8 %
- 24. SHUTDOWNS SCHEDULED OVER THE NEXT 6 MONTHS (TYPE DATE AND DURATION OF EACH):
- 25. IF SHUTDOWN AT THE END OF REPORT PERIOD, ESTIMATED DATE OF STARTUP:
- 26. UNITS IN TEST STATUS (PRIOR TO COhWERCIAL OPERATIONS):
FORECAST ACHIEVED INITIAL CRITICALITY 0807/74 INITIAL ELECTRICITY 0001/74 COMMERCIAL OPERATION 12/23f74 PAGE 2 OF 2
.m..-.
E UNIT SHUTDOWNS AND POWER REDUCTIONS DOCKET NO. 50-2T/
UNIT NAME PEACH BOTTOM UNIT 2 DATE JULY 11,1996 COMPLETED BY PECO ENERGY COMPANY L P. HYDRICK BUSINESS SERVICES SITE SUPPORT DIVISION PEACH BOTTOM ATOMIC POWER STATION REPORT MONTH JUNE,1996 TELEPHONE (717)456-4383 METHOD OF UCENSEE SYSTEM COMPONENT CAUSE AND CORRECTIVE TYPE DURATION REASON SHUTTING DOWN EVENT CODE CODE ACTION TO NO.
DATE (1)
(HOURS)
(2)
REACTOR (3)
REPORT #
(4)
(S)
PREVENT RECURRENCE 19 960604 F
S.0 H
4 ZZ 777777 220-08 UNE DE-ENERGtZED REACTOR NOT SHUT DOWN.
20 960609 S
4.0 H
4 CH PUMPXX REMOVED RFP FROM SERVICE. REACTOR NOT SHUT DOWN.
TOTAL HOURS 9.0 t
I (1)
(2)
(3)
(4)
F-FORCED REASON METHOD EXHIBIT G-INSTRUCTIONS S - SCHEDULED A - EQUIPMENT FAILURE (EXPLAIN) 1 - MANUAL FOR PREPARATION OF DATA B-MAINTENANCE OR TEST 2-MANUAL SCRAM ENTRY SHEETS FOR UCENSEE C-REFUEUNG 3-AUTOMATIC SCRAM EVENT REPORT (LER)
D-REGULATORY RESTRICTION 4-OTHER (EXPLAIN)
FILE (NUREG4161)
E-OPERATOR TRAIMNG + UCENSE EXAMINATION F - ADMINISTRATIVE (5)
G-OPERATIONAL ERROR (EXPLAIN)
EXHIBIT I-SAME SOURCE H -OTHER (EXPLAIN)
UNIT SHUTDOWNS AND POWER REDUCTIONS t
~
DOCKET NO. 50-278 UNIT NAME PEACH BOTTOM UNIT 3 DATE JULY 11,1996 COMPLETED BY PECO ENERGY COMPANY L P.HYDRICK -
BUSINESS SERVICES -
j t
SITE SUPPORT DIVISION PEACH BOTTOM ATOMIC POWER STATION REPOP.T MONTH JUNE,1996 TELEPHONE (717)456-4383 METHOD OF LICENSEE SYSTEM COMPONENT CAUSE AND CORRECTIVE TYPE DURATION REASON SHUTTING DOWN EVENT CODE CODE ACTION TO NO.
DATE (1)
(HOURS)
(2)
REACTOR (3)
REPORT #
(4)
(5)
PREVENT RECURRENCE 14 900001 S
54.0 B
4 CD VALVEX MSIV TESTING, MG SET MAINT., RFP MAINT.
[
REACTOR NOT SHUT DOWN 15 900622 S
25.0 B
4 CD VALVEX REPAIR 84 CV EAC LEAK AND MSV LEAK. REACTOR NOT SHUT DOWN.
16 900623 F
1 91.0 A
2 CD VALVEX REPAIR #2 TURBINE CONTROL VALVE STEM.
TOTAL HOURS 270.0 l
i
'f (1)
(2)
(3)
(4)
F-FORCED REASON METHOD EXHIBIT G-INSTRUCTIONS S - SCHEDULED A-EQUIPMENT FAILURE (EXPLAIN) 1 - MANUAL FOR PREPARATION OF DATA B -MAINTENANCE OR TEST 2-MANUAL SCRAM ENTRY SHEETS FOR LICENSEE C-REFUELING 3-AUTOMATIC SCRAM EVENT REPORT (LER)
D-REGULATORY RESTRICTION 4-OTHER (EXPLAIN)
FILE (NUREG4161)
E - OPERATOR TRAINING + LICENSE EXAMINATION F-ADMINISTRATNE (5)
G-OPERATIONAL ERROR (EXPLAIN)
EXHIBITI-SAME SOURCE H -OTHER (EXPLAIN)
.. -